ENTRY 21330 20200925 22912133000000001 SUBENT 21330001 20200925 22912133000100001 BIB 13 35 2133000100002 TITLE Gamma rays from neutron inelastic scattering in 2133000100003 germanium 2133000100004 AUTHOR (J.F.Barry) 2133000100005 REFERENCE (C,66PARIS,1,365,1966) Abstract of CN-23/59. 2133000100006 (S,INDC-156,(CN-23/59),1967) Supplement to the 2133000100007 Proceedings of a Conference, Paris, 17-21 Oct.1966 2133000100008 - data only on figs. 2133000100009 INSTITUTE (2UK ALD) 2133000100010 FACILITY (VDG,2UK ALD) 2133000100011 INC-SOURCE (D-T) Tritium gas cell through a 2 mg/cm2 nickel 2133000100012 window which was supported on a gold grid. 2133000100013 INC-SPECT (EN-RSL-HW) Energy spread value 2133000100014 SAMPLE The germanium crystal used as both target and detector 2133000100015 had. an area of ~ 1.5 cm2 and a thickness of ~1 cm. 2133000100016 METHOD Detection of inelastic gammas. The cross section for 2133000100017 inelastic scattering to the pair of levels near 5 2133000100018 80 keV using a neutron detection method. 2133000100019 DETECTOR (GELI) 2133000100020 (FISCH) The neutron flux at each energy was measured 2133000100021 with a fission counter containing a known mass of 237Np2133000100022 (LONGC) A long counter 1.5 m from the target monitored 2133000100023 neutrons from the reaction at 45. degr. 2133000100024 CORRECTION Corrections were made to the neutron flux deduced at 2133000100025 the detector position to allow for neutron attenuation 2133000100026 and scattering. The attenuation of neutrons in the 2133000100027 aluminium vacuum container was calculated to be 4.5% 2133000100028 scattering from the cold finger materials 4%. 2133000100029 ERR-ANALYS (ERR-1) error from neutron flux determination 2133000100030 (ERR-2,2.,10.) error due gamma-ray yield determination 2133000100031 HISTORY (19800206T) 2133000100032 (20170805A) SD:Updated to new date formats, lower case.2133000100033 Meaningless zeros were deleted from the data. Refs 2133000100034 update. BIB update. 2133000100035 (20200925A) SD: Corrections in all Subents. BIB updated2133000100036 EN-RSL -> EN-RSL-HW. 2133000100037 ENDBIB 35 0 2133000100038 COMMON 2 3 2133000100039 EN-RSL-HW ERR-1 2133000100040 KEV PER-CENT 2133000100041 50. 10. 2133000100042 ENDCOMMON 3 0 2133000100043 ENDSUBENT 42 0 2133000199999 SUBENT 21330002 20200925 22912133000200001 BIB 4 8 2133000200002 REACTION (32-GE-73(N,INL)32-GE-73,PAR,SIG,G,A) 2133000200003 MONITOR (32-GE-0(N,INL)32-GE-0,PAR,SIG) Cross section for 2133000200004 excitation of 565 keV level in Ge-76 and 595 keV level2133000200005 in Ge-74 in natural Ge taken as 0.36 barns 2133000200006 at 1 MeV from private communication of A.B.Smith. 2133000200007 STATUS (NDD) 2133000200008 HISTORY (20200925A) SD: SF1=SF4=Ge-76 -> Ge-0 in MONITOR code. 2133000200009 EN-NRM, E-NRM1/NRM2 added. 2133000200010 ENDBIB 8 0 2133000200011 COMMON 5 3 2133000200012 EN-NRM E E-NRM1 E-NRM2 MONIT 2133000200013 MEV KEV KEV KEV B 2133000200014 1. 365. 565. 595. 0.36 2133000200015 ENDCOMMON 3 0 2133000200016 DATA 2 13 2133000200017 EN DATA 2133000200018 MEV B 2133000200019 0.60 0.019 2133000200020 0.65 0.031 2133000200021 0.70 0.044 2133000200022 0.73 0.037 2133000200023 0.76 0.036 2133000200024 0.79 0.045 2133000200025 0.89 0.068 2133000200026 0.95 0.042 2133000200027 1.00 0.080 2133000200028 1.03 0.068 2133000200029 1.08 0.049 2133000200030 1.25 0.068 2133000200031 1.70 0.065 2133000200032 ENDDATA 15 0 2133000200033 ENDSUBENT 32 0 2133000299999 SUBENT 21330003 20200925 22912133000300001 BIB 4 6 2133000300002 REACTION (32-GE-72(N,INL)32-GE-72,PAR,SIG,G,REL) 2133000300003 STATUS (NDD) 2133000300004 COMMENT Gamma line due to 100% isomeric transition. 2133000300005 Uncertainty in depletion depth in Ge(Li) makes 2133000300006 normalization impossible. 2133000300007 HISTORY (20200925U) SD: BIB updated. ERR-ANALYS -> COMMENT. 2133000300008 ENDBIB 6 0 2133000300009 COMMON 1 3 2133000300010 E 2133000300011 KEV 2133000300012 695. 2133000300013 ENDCOMMON 3 0 2133000300014 DATA 2 20 2133000300015 EN DATA 2133000300016 MEV ARB-UNITS 2133000300017 0.60 0.000 2133000300018 0.65 0.000 2133000300019 0.70 0.013 2133000300020 0.73 0.039 2133000300021 0.76 0.088 2133000300022 0.79 0.134 2133000300023 0.84 0.199 2133000300024 0.89 0.238 2133000300025 0.95 0.259 2133000300026 1.00 0.286 2133000300027 1.03 0.319 2133000300028 1.08 0.350 2133000300029 1.13 0.337 2133000300030 1.20 0.356 2133000300031 1.25 0.336 2133000300032 1.36 0.327 2133000300033 1.50 0.339 2133000300034 1.70 0.293 2133000300035 2.00 0.280 2133000300036 2.43 0.231 2133000300037 ENDDATA 22 0 2133000300038 ENDSUBENT 37 0 2133000399999 SUBENT 21330004 20200925 22912133000400001 BIB 3 3 2133000400002 REACTION (32-GE-76(N,INL)32-GE-76,PAR,SIG,G,REL) 2133000400003 STATUS (NDD) 2133000400004 HISTORY (20200925U) SD: BIB updated. 2133000400005 ENDBIB 3 0 2133000400006 COMMON 1 3 2133000400007 E 2133000400008 KEV 2133000400009 565. 2133000400010 ENDCOMMON 3 0 2133000400011 DATA 2 20 2133000400012 EN DATA 2133000400013 MEV ARB-UNITS 2133000400014 6.0000E-01 1.0600E-01 2133000400015 6.5000E-01 3.1400E-01 2133000400016 7.0000E-01 3.7000E-01 2133000400017 7.3000E-01 4.1800E-01 2133000400018 7.6000E-01 4.9200E-01 2133000400019 7.9000E-01 7.5100E-01 2133000400020 8.4000E-01 6.4600E-01 2133000400021 8.9000E-01 6.2400E-01 2133000400022 9.5000E-01 7.6700E-01 2133000400023 1.0000E+00 9.6800E-01 2133000400024 1.0300E+00 7.7000E-01 2133000400025 1.0800E+00 8.9200E-01 2133000400026 1.1300E+00 1.1300E+00 2133000400027 1.2000E+00 9.2500E-01 2133000400028 1.2500E+00 1.1760E+00 2133000400029 1.3600E+00 9.8100E-01 2133000400030 1.5000E+00 1.0210E+00 2133000400031 1.7000E+00 1.2800E+00 2133000400032 2.0000E+00 8.1800E-01 2133000400033 2.4300E+00 4.9200E-01 2133000400034 ENDDATA 22 0 2133000400035 ENDSUBENT 34 0 2133000499999 SUBENT 21330005 20200925 22912133000500001 BIB 4 8 2133000500002 REACTION (32-GE-70(N,INL)32-GE-70,PAR,SIG,G,A) 2133000500003 MONITOR (32-GE-0(N,INL)32-GE-0,PAR,SIG) Cross section for 2133000500004 excitation of the 565 and 595 keV levels in Ge-76 2133000500005 and in Ge-74 from irradiation of natural germanium 2133000500006 as 0.36 B from private communication of A.B.Smith. 2133000500007 STATUS (NDD) 2133000500008 HISTORY (20200925A) SD: SF1=SF4=Ge-76 -> Ge-0 in MONITOR code. 2133000500009 EN-NRM, E-NRM added. 2133000500010 ENDBIB 8 0 2133000500011 COMMON 5 3 2133000500012 EN-NRM E E-NRM E-NRM MONIT 2133000500013 MEV KEV KEV KEV B 2133000500014 1. 1040. 565. 595. 0.36 2133000500015 ENDCOMMON 3 0 2133000500016 DATA 2 10 2133000500017 EN DATA 2133000500018 MEV B 2133000500019 1.03 0.000 2133000500020 1.08 0.052 2133000500021 1.13 0.112 2133000500022 1.20 0.142 2133000500023 1.25 0.181 2133000500024 1.36 0.266 2133000500025 1.50 0.308 2133000500026 1.70 0.280 2133000500027 2.00 0.274 2133000500028 2.43 0.250 2133000500029 ENDDATA 12 0 2133000500030 ENDSUBENT 29 0 2133000599999 SUBENT 21330006 20200925 22912133000600001 BIB 4 8 2133000600002 REACTION (32-GE-74(N,INL)32-GE-74,PAR,SIG,G,A) 2133000600003 MONITOR (32-GE-0(N,INL)32-GE-0,PAR,SIG) Cross section for 2133000600004 excitation of 565 level in Ge-76 and 595 level in 2133000600005 Ge-74 taken as 0.36 b from private communication of 2133000600006 A.B.Smith. 2133000600007 STATUS (NDD) 2133000600008 HISTORY (20200925A) SD: SF1=SF4=Ge-76 -> Ge-0 in MONITOR code. 2133000600009 EN-NRM, E-NRM added. 2133000600010 ENDBIB 8 0 2133000600011 COMMON 5 3 2133000600012 EN-NRM E E-NRM E-NRM MONIT 2133000600013 MEV KEV KEV KEV B 2133000600014 1. 595. 565. 595. 0.36 2133000600015 ENDCOMMON 3 0 2133000600016 DATA 2 20 2133000600017 EN DATA 2133000600018 MEV B 2133000600019 0.60 0.034 2133000600020 0.65 0.034 2133000600021 0.70 0.267 2133000600022 0.73 0.380 2133000600023 0.76 0.480 2133000600024 0.79 0.639 2133000600025 0.84 0.676 2133000600026 0.89 0.695 2133000600027 0.95 0.756 2133000600028 1.00 0.779 2133000600029 1.03 0.839 2133000600030 1.08 0.826 2133000600031 1.13 0.889 2133000600032 1.20 0.751 2133000600033 1.25 0.821 2133000600034 1.36 0.934 2133000600035 1.50 0.956 2133000600036 1.70 0.983 2133000600037 2.00 0.781 2133000600038 2.43 0.716 2133000600039 ENDDATA 22 0 2133000600040 ENDSUBENT 39 0 2133000699999 ENDENTRY 6 0 2133099999999